ML20070P053

Draft Tech Specs Re Operability of Auxiliary Feedwater Sys

ML20070P053
Person / Time
Site:	Calvert Cliffs
Issue date:	01/17/1983
From:	BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20070P052	List: ML20070P051 ML20070P053
References
NUDOCS 8301260087
Download: ML20070P053 (5)

Text

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4 ATTACHMENT 1 PLANT SYSTEMS I

BASES ~ ,-

i U = Maximum number of inoperable safety valves per operating steam line ,

106.) = Power Level-High Trip Setpoint for two loop operation

46.8 = Power Level-High Trip Setpoint for single loop operation with i two reactor coolant pumps operating in the same loop X = Total relieving capacity of all safety valves per steam line in Ibs/ hour Y = Maximum relieving capacity of any one safety valve in Ibs/ hour 1

3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the auxiliary feedwaty system ensures that the Reactor Coolant System can be cooled down to less than 300 F from normal operating conditions in the event of a total loss of offsite power. A capacity of 400 gpm is sufficient to ensure that adequate feedwater flow is available to regve decay heat and reduce the Reactor Coolant System temperature to less than 300 F when the shutdown cooling system may be placed into operation.

Flow control valves, installed in each Ng supplying the steam generators, maintain a l

nominal flow setpoint of 320 gpm plus or minus 10 gpm for operator setting band. The i nominal flow setpoint of 320 gpm incorporates a total instrument loop error band of plus 47 gpm (377 gpm total flow per leg) and minus 60 gpm (250 gpm total flow per leg).

j In the spectrum of events analyzed in which automatic initiation of auxiliary feedwater j occurs the nominal setting of 320 gpm allows a minimum of 10 minutes before operator action is required. At 10 minutes after automatic initiation of flow the operator is assumed to be available to increase or decreaf.e auxiliary feedwater flow to that required for existing plant conditions.

4 CALVERT CLIFFS UNIT-2 B 3/4 7-2 Amendment No.

8301260087 830117 PDRADOCK05000g P

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ATTACHMENT 2 TABLE 3.3-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

6. Steam Generator Pressure-Low

a. Main Steam Isolation 6 6.9

b. Feedwater Isolation i 80

7. Refueling Water Tank-Low

a. Containment Sump Recirculation d 80

8. Reactor Trip

a. Feedwater Flow Reduction to 5% 6 20

9. Loss of Power

a. 4.16 kv Emergency Bus Undervoltage 4 2.2* * *

(Loss of Voltage)

b. 4.16 kv Emergency Bus Undervoltage A8.4***

(Degraded Voltage) l

10. Steam Generator Level- Low I

a. Steam Driven AFW Pump 154.5 l l

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11. Steam Generatorb P-High '

a. Auxiliary Feedwater Isolation i 20.0 j TABLE NOTATION l

Diesel generator starting and sequence loading delays included.

Diesel generator starting and sequence loading delays not included.

Offsite power available.

• • • Response time measured from the incidence of the undervoltage condition to the diesel generator start signal.

CALVERT CLIFFS - UNIT 2 3/4 3-21 Amendment No.

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ATTACHMENT 3 i TABLE 3.3-10 1

POST-ACCIDtiNT MONITORING IN5TRUMENTATION i1 4

MINIMUM CHANNELS INSTRUMENT OPERABLE

1. Containment Pressure 2

2. Wide Range Logarithmic Neutron Flux Monitor 2

3. Reactor Coolant Outlet Temperature 2

4. Pressurizer Pressure 2 i

5. Pressurizer Level 2

6. Steam Generator Pressure 2/ steam generator

7. Steam Generator Level (Wide Range) 2/ steam generator

8. Auxiliary Feedwater Flow Rate 1/ steam generator

9. RCS Subcooled Margin Monitor 1

! 10. PORV/ Safety Valve Acoustic Flow Monitoring 1/ valve

11. PORY Solenoid Powe1 Indication 1/ valve 1 -

1

.. . .o PLANT SYSTEMS ATTACHMENT 4 AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION-3.7.1.2 At least two steam turbine driven steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE.

APPLICABILITY: MODES 1,2, and 3.

ACTION:

a. With one steam driven pump inoperable restore at least two steam d-iven pumps to OPER ABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN with. 6 the next 12 -

hours.

b. Whenever a subsystem (consisting of one pump, piping, valves and controls in the direct flow path) required for operability is inop~erable for the performance of periodic testing (e.g. manual discharge valve closed for pump Total Dynamic Head test) a dedicated operator will be stationed at the local station with direct communication to the Control Room. Upon completion of any testing, the subsystem required for operability will be returned to its proper status and verified in its proper status by an independent operator check.

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CALVERT CLIFFS-UNIT 2 3/47-5 Amendment No.

ATTACHMENT 5 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater flowpath shall be demonstrated nPERABLE:

a. At least once per 31 days by:

1. Verifying that each steam driven pump develops a Total Dynamic Head of 2 2800 ft. on recirculation flow. (If verification must be demonstrated during startup, surveillance t9 ting shall be performed upon achievine an RCS temperature 2 300 F and prior to entering MODE 1).

2. Cycling each testable, remote operated valve that is not in its operating position through at least one complete cycle.

3. Verifying that each valve (manual, pouer operated or automatic) in the direct flow path is in its correct position. The AFW flow control valves may be verified by observing a 320 gpm setpoint on the flow indicator controller in Control Room.

b. Before entering MODE 3 after a COLD SHUTDOWN of at least 14 days by completing a flow test that verifies the flow path from the condensate storage tank to the steam generators.

c. At least once per 18 months by verifying that each automatic valve in the flow path actuates to its correct position and each auxiliary feedwater pump autcmatically starts and delivers a modulated flow of 320 gpm + 10 gpm to each flow leg upon receipt of each auxiliary feedwater actuation system (AFAS) test signal.

CALVERT CLIFFS-UNIT 2 3/4 7-Sa Amendment No.

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